The environmental impact assessment process for nuclear facilities: A review of the Lithuanian practice and experience

Ragaisis, V.; Poškas, Povilas; Šimonis, Vytautas; Smaizys, Arturas; Kilda, Raimondas; Grigaliuniene, Dalia

doi:10.1016/j.pnucene.2014.01.014

Cited by 8 publications

(2 citation statements)

References 5 publications

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“…The impact of radiation to human health [20,21] and risk [22,23] are indicated by dose parameter that figure out interaction between radiation with human tissue. Radionuclides that reach the ground surface can irradiate humans as clouds in which humans are immersed in it.…”

Section: Dose Calculation Model From External Exposure or Cloudmentioning

confidence: 99%

Preliminary Development of Radionuclides Release of Individual Dose Code Program for Radiation Monitoring Purposes

Pane

Udiyani²,

Setiawan³

et al. 2021

Tri Dasa Mega

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Environmental radiation monitoring is one of the important efforts in protecting society and the environment from radiation hazards, both natural and artificial. The presence of three nuclear research reactors and plans to build a nuclear power plant reactor prompted Indonesia to prepare a radiation monitoring system for safety and security (SPRKK). The goal of the study is to provide an appropriate method for developing radiation monitoring system to support the development of nuclear power plant in the near future. For this preliminary study, the author developed a code program using Gaussian distribution model approach for predicting radionuclide release and individual dose acceptancy by human being within 16 wind directions sectors and up to 50 km distance. The model includes estimation of source term from the nuclear installation, release of radionuclides source into air following Gaussian diffusion model, some of the release deposit to the land and entering human being through inhalation, direct external exposure, and resuspension, and predicted its accepted individual dose. This model has been widely used in various code program such as SimPact and PC-Cosyma. For this study, the model will be validated using SimPact code program. The model has been successfully developed with less than 5% deviation. Further study will be done by evaluating the model with real measuring data from research reactor installation and prepare for interfacing with real time radiation data acquisition and monitoring as part of radiation monitoring system during normal and accident condition.

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Section: Dose Calculation Model From External Exposure or Cloudmentioning

confidence: 99%

Preliminary Development of Radionuclides Release of Individual Dose Code Program for Radiation Monitoring Purposes

Pane

Udiyani²,

Setiawan³

et al. 2021

Tri Dasa Mega

View full text Add to dashboard Cite

show abstract

“…With various pathways such as cloud-shine, groundshine, and foodstuff, human doses are received internally (inhalation, immersion and consumption) and externally [7][8][9]. The calculation uses PC-CREAM software [1,10], which works based on segmented Gaussian [11][12]. Environmental and meteorological data were obtained using Arc-GIS and spatial analysis.…”

Section: Introduction mentioning

confidence: 99%

Environmental Consequences of Routine Releases From Small Medium Reactor at Babel Site

et al. 2021

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Radiation protection and safety documents for routine conditions are required to support the licensing requirements for nuclear power plant site. This research is focused in the assessment and analysis of the results of PWR safety study related to the routine release of radioactivity from the SMR subsystems and components of the 100 MWe-type PWR along with its consequences in the site. The core inventory calculation was done using ORIGEN2 software, applying release parameters from the existing analysis and calculation results. The radiological consequences were calculated by the PC-CREAM program package. Environmental and meteorological data were obtained using Arc-GIS and spatial analysis. The Bangka Belitung (Babel) site was used as the specific footprint. Analyzing PC-CREAM output data the radiological consequences of routine operation of 3 100 MWe PWR modules on Sebagin site (South Bangka) and Muntok site (West Bangka) in 16 sectors and within a radius of 20 km were concluded. The calculation results for the Sebagin site is that the maximumdose within a radius of 500 m (exclusion zone) is 1.15E+02 µSv/year. For a radius beyond 500 m, the maximum dose is 4.71E+01 µSv/year. Whereas for Muntok site (West Bangka), the maximum dose in the exclusion area (<500m) is 9.47E+00 µSv/year, and outside exclusion area (>500m) is 3.10E+00 µSv/year. The individual dose for the Babel site in the exclusion area is below the dose constraint for non-radiation service workers as the general public of 0.3 mSv/year or 300 µSv/year, while the maximum dose for outside exclusion is also below the constraint as stipulated in BAPETEN Regulation No 4 Year 2013 on Radiation Protection and Safety.

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Progress on Nuclear Waste Management

Poškas

2018

Challenges of Nuclear Waste Governance

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The environmental impact assessment process for nuclear facilities: A review of the Lithuanian practice and experience

Cited by 8 publications

References 5 publications

Preliminary Development of Radionuclides Release of Individual Dose Code Program for Radiation Monitoring Purposes

Preliminary Development of Radionuclides Release of Individual Dose Code Program for Radiation Monitoring Purposes

Environmental Consequences of Routine Releases From Small Medium Reactor at Babel Site

Progress on Nuclear Waste Management

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